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Event Notification Report for February 10, 2003






                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           02/07/2003 - 02/10/2003



                              ** EVENT NUMBERS **



39573  39574  



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39573       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/07/2003|

|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 15:54[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/07/2003|

+------------------------------------------------+EVENT TIME:        14:08[EST]|

| NRC NOTIFIED BY:  ROBERT G. HADDOCK            |LAST UPDATE DATE:  02/07/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JAMES NOGGLE         R1      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| UNANALYZED CONDITION RELATED TO A POTENTIAL DISCHARGE OF THE C02 FIRE        |

| SUPPRESSION SYSTEM                                                           |

|                                                                              |

| "On 2/7/2003 at 1408 hours, the Beaver Valley Power Station control room was |

| notified by Engineering that a potential pressure transient from a discharge |

| of the C02 total flooding fire suppression system in the East and West Cable |

| Vaults at Beaver Valley Unit 1 (BV-1) could result in an unanalyzed          |

| condition. This pressure transient could cause the fire barriers within the  |

| subject areas to be structurally challenged, resulting in the potential for  |

| a postulated fire in one fire area to spread to an adjacent fire area. This  |

| condition could invalidate the assumptions made in the BV-1 fire protection  |

| safe shutdown analysis per 10 CFR 50 Appendix R. This condition was          |

| discovered following engineering's evaluation of a Condition Report          |

| initiated on 2/5/03 concerning the potential for a C02 discharge in the      |

| above areas that could have resulted in a breach of the fire barriers        |

| between adjacent fire areas. The automatic C02 suppression system in the     |

| East and West Cable Vaults was defeated on 2/5/03 at 2150 hours in response  |

| to the initial identified concern and a fire watch was established in the    |

| affected areas. These compensatory measures eliminate the potential for C02  |

| overpressure transient condition in the affected areas.                      |

|                                                                              |

| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an   |

| unanalyzed condition that significantly degrades plant safety since a        |

| potential discharge of the C02 fire suppression system in response to a      |

| postulated fire could have invalidated the assumptions made in the BV-1 fire |

| protection safe shutdown analysis per 10 CFR 50 Appendix R. The NRC resident |

| has been notified of the degraded condition."                                |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Other Nuclear Material                           |Event Number:   39574       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  INDIANA DEPARTMENT OF TRANSPORTATIO  |NOTIFICATION DATE: 02/09/2003|

|LICENSEE:  INDIANA DEPARTMENT OF TRANSPORTATION |NOTIFICATION TIME: 07:10[EST]|

|    CITY:  INDIANAPOLIS             REGION:  3  |EVENT DATE:        02/09/2003|

|  COUNTY:                            STATE:  IN |EVENT TIME:        04:20[EST]|

|LICENSE#:  13-26341-01           AGREEMENT:  N  |LAST UPDATE DATE:  02/09/2003|

|  DOCKET:  03032463                             |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |KENNETH RIEMER       R3      |

|                                                |MELVYN LEACH         NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  TOM JOHN                     |                             |

|  HQ OPS OFFICER:  RICH LAURA                   |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NINF                     INFORMATION ONLY       |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| DAMAGED TROXLER GAUGE AT CONSTRUCTION SITE                                   |

|                                                                              |

| The RSO from the Indiana Department of Transportation reported a damaged     |

| Troxler gauge at a new construction site located approximately 1 mile west   |

| of the Indianapolis Airport.  A bulldozer drove over the Troxler gauge.  The |

| gauge belongs to the State of Indiana. The gauge was a model number 3440 and |

| had the serial number 19699.   The gauge contained approximately 8           |

| millicuries Cs-137 and 40 millicuries of Am-241/Be.  The operating rod       |

| handle on the top of the gauge was bent over such that the plate on the      |

| bottom was stuck open.  The RSO performed a radiological survey.  The gauge  |

| casing was intact and no leakage was found.  No personnel contaminations or  |

| radiation overexposures were observed.  The RSO roped off the area. The RSO  |

| planned to transport the gauge back to the facilities shielded room.         |

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